DocumentCode
2040550
Title
Design consideration on ex-vessel neutron yield monitor for ITER
Author
Asai, Kikuo ; Iguchi, Toshio ; Nishitani, Takashi
Author_Institution
Dept. of Nucl. Eng., Nagoya Univ., Aichi, Japan
fYear
2003
fDate
5-5 June 2003
Firstpage
484
Abstract
Summary form only given, as follows. Neutron yield measurement is one of the most important plasma diagnostic system in DD and/or DT fusion experiments and allows an absolute measure of the fusion power. In ITER experiments, main characteristics required for the neutron yield monitor are (1) real-time measurement (1ms time resolution), (2) stable and robust operation with high-reliability and redundancy in a hostile environment, (3) neutron-gamma rays discrimination characteristic, (4) wide dynamic range(from 8 to 11 orders of magnitude) and (5) appropriate detection efficiency characteristic for absolute measurement of total neutron yield, which means as a flat energy detector response as possible. To meet these requirements we propose a neutron yield monitor based on U-235 fission chambers with neutron moderators to be installed outside the vacuum vessel, which is routinely used at other tokamaks.
Keywords
Tokamak devices; calibration; fission counters; fusion reactor instrumentation; neutron detection; neutron moderation; plasma diagnostics; ITER; absolute measurement; detection efficiency; ex-vessel neutron yield monitor; fission chambers; flat energy detector response; fusion power; high-reliability; in-situ calibration; neutron moderators; neutron-gamma rays discrimination; plasma diagnostic; real-time measurement; tokamaks; total neutron yield; Dynamic range; Energy measurement; Energy resolution; Monitoring; Neutrons; Plasma diagnostics; Plasma measurements; Power measurement; Robustness; Time measurement;
fLanguage
English
Publisher
ieee
Conference_Titel
Plasma Science, 2003. ICOPS 2003. IEEE Conference Record - Abstracts. The 30th International Conference on
Conference_Location
Jeju, South Korea
ISSN
0730-9244
Print_ISBN
0-7803-7911-X
Type
conf
DOI
10.1109/PLASMA.2003.1230100
Filename
1230100
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